ML19309B226
| ML19309B226 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/21/1980 |
| From: | Counsil W, Fee W NORTHEAST UTILITIES |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-06-07.A3, TASK-06-07.B, TASK-06-10.A, TASK-07-01.A, TASK-07-02, TASK-6-10.A, TASK-6-7.A3, TASK-6-7.B, TASK-7-1.A, TASK-7-2, TASK-RR NUDOCS 8004030293 | |
| Download: ML19309B226 (3) | |
Text
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March 21,1980 Docket Nos. 50-213 50-2h5 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactora Branch #2 U. G. Nuclear Regulatory Commission Washington, D. C.
20555
References:
(1)
D. L. Ziemann letter to W. G. Council dated February lh, 1980.
(2)
D. L. Ziemann letter to W. G. Counsil dated February 14, 1980.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Gtation, Unit No. 1 GFP References to Docketed Information In Referencen (1) and (2), Connecticut Yankee Atomic Power Company (CYAPCO) and Northeact Nuclear Energy Company (UNECO) were requected to provide a list of referencea for the five SEP topien identified in the above lettera.
In fulfill-ment of that request, Attachmente 1 and 2 for CYAPCO and NUECO, respectively, are provided.
Inclumed in the Attachments are the topic number, title, and linting of the references identified to date.
Pleane recognize that numerouc other NRC Staff requents have been designr.ted a higher priority than the responce to References (1) and (2). As such, the attached listing does not reflect an exhaustive review of our docketed correspondence, but only that rerdily identified.
In the event the Gtaff or its consultanto have cpecific additional informational needs, we would be happy to provide answers upon receipt of those requesta.
Very truly yours, CONNECTICVf (ANKEE ATOMIC POWER CO' PANY NORTHEAUT NUCLEAR FNERGY COMPAfd a
W. G. 6funcil Vice President Attaclnenta W. F. Fee V I.c < President 8004 030 Qy g
MILLSTONE UNIT NO.1 TOPIC REFERENCES VI-7. A.3 -- ECCS Actuation System Technical Specification Sections 3.2.B 3.5, and Bases e
FSAR Section VI.2, VII.4 e
VI-7.B -- ESF Switchover From Injection to Recirculation Mode i
(Automatic ECCS Realignment )
e NOT APPLICABLE I
VI-10. A -- Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing e
Technical Specification Sections 3.1, 4.1, 3.2, 4.2, 3.3, h.3, and Bases i
e FSAR Section VII.2, VI l
I VII-1. A -- Isolation of Reactor Protection System From Non-Safety Systems, Including Qualification of Isolation Devices W. G. Counsil letter to B. H. Grier dated February 29, 1980, responding e
l to I&E Bulletin No. 79-27 VII-2 -- Engineered Safety Features (ESP) System Control Logic and Design e FSAR Section VI.
2 i
l l
l l
l 1
4.'
HADDAM NECK PLANT
'IOPIC REFERENCES i
. VI-7. A.3 - ECCS Actuation System Technical Specification Sections 3.6, 3 9, and 4.3 e
e - FDSA Section 5 2.7 1
VI-7.B -- ESF Switchover From Injection to Recirculation Mode (Automatic ECCS Realignment)
A series. of telecopied 'information requests, subsequent responses, and e
associated telephone discussions took place during December of 1978 j
and the Spring of 1979 This -information was not docketed but all NRC Staff requests were responded to.
I VI-10. A -- Testing of Reactor Trip System and Engineered Safety Features, Including Response Time Testing e FDSA Section 11.h.9 Technical Specification Section 2.4 e
j
.VII-1. A -- Isolation of Reactor Protection System From Hon-Safety Systems, Including Qualification of Isolation Devices 3
.1 e
W. G. Counsil letter to B. H. Grier dated March 3,1980, responding to i
I&E Bulletin No. 79-27 t
VII-2 -- Engineered Safety Features (ESF) System Control Logic and Design e-4 J
J W
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